Evaluation of reactor internals integrity and lifetime according to the NTD ASI

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F18%3AN0000030" target="_blank" >RIV/46356088:_____/18:N0000030 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1115/PVP2018-84140" target="_blank" >http://dx.doi.org/10.1115/PVP2018-84140</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1115/PVP2018-84140" target="_blank" >10.1115/PVP2018-84140</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Evaluation of reactor internals integrity and lifetime according to the NTD ASI

Popis výsledku v původním jazyce

Reactor internals are components that are no typical pressure boundary but they are nevertheless very important as they hold fuel elements and all reactor control system elements and thus must ensure their safe and reliable operation during the whole reactor life under all operating and even beyond bases regimes. In principle, reactor internals can be replaced but their weight, quantity of very high activated material and cost such possibility practically excluded. Thus, evaluation of the reactor internals condition and prediction of their behavior during the whole or even extended lifetime is of high importance. Reactor internals are subjected to very high neutron irradiation that could initiated not only stress corrosion (irradiation assisted) cracking but also large embrittlement and changes in dimensions (swelling and creep). VERLIFE – „Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs during Operation“was initiated and co-ordinated by the Czech and was developed within the 5th Framework Program of the European Union in 2003 and later upgraded within the 6th Framework Program „COVERS – Safety of WWER NPPs“of the European Union in 2008. This Procedure had to fill the gap in original Soviet/Russian Codes and Rules for Nuclear Power Plants (NPPs) with WWER (Water-Water-Energetic-Reactor = PWR type) type reactors, as those codes were developed only for design and manufacture and were not changed since their second edition in 1989. VERLIFE Procedure is based on these Russian codes but incorporates also new developments in research, mainly in fracture mechanics, and also some principal approaches used in PWR codes.Within the last upgrading and principal extending of this VERLIFE Procedure was developed within the 3-years IAEA project (in close co-operation with another project of the 6th Framework Program of the European Union “NULIFE – Plant Life Management of NPPs”) that started in 2009 with final approval and editing in 2013”) a part dealing with the evaluation of reactor internals lifetime was elaborated.. This IAEA VERLIFE procedure for internals has been implemented into the existing Normative Technical Documentation (NTD) ASI (Czech Association of Mechanical Engineers), Section IV – Evaluation of Residual Lifetime of Components and Piping in WWER type NPPs. Main damaging mechanisms that should be taken into account in reactor internals and the procedure are described in detail with necessary formulae for materials of internals: - Radiation hardening - Radiation embrittlement - Radiation swelling - Radiation creep - Swelling under stress effect - Swelling inducing embrittlement - Irradiated assisted stress corrosion cracking - Transformation austenite-ferrite and also the method for evaluation of the resistance against non-ductile failure of postulated defect. The paper will describe these main principles and also more detailed information on the procedure for evaluation of reactor internals will be given.

Název v anglickém jazyce

Evaluation of reactor internals integrity and lifetime according to the NTD ASI

Popis výsledku anglicky

Reactor internals are components that are no typical pressure boundary but they are nevertheless very important as they hold fuel elements and all reactor control system elements and thus must ensure their safe and reliable operation during the whole reactor life under all operating and even beyond bases regimes. In principle, reactor internals can be replaced but their weight, quantity of very high activated material and cost such possibility practically excluded. Thus, evaluation of the reactor internals condition and prediction of their behavior during the whole or even extended lifetime is of high importance. Reactor internals are subjected to very high neutron irradiation that could initiated not only stress corrosion (irradiation assisted) cracking but also large embrittlement and changes in dimensions (swelling and creep). VERLIFE – „Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs during Operation“was initiated and co-ordinated by the Czech and was developed within the 5th Framework Program of the European Union in 2003 and later upgraded within the 6th Framework Program „COVERS – Safety of WWER NPPs“of the European Union in 2008. This Procedure had to fill the gap in original Soviet/Russian Codes and Rules for Nuclear Power Plants (NPPs) with WWER (Water-Water-Energetic-Reactor = PWR type) type reactors, as those codes were developed only for design and manufacture and were not changed since their second edition in 1989. VERLIFE Procedure is based on these Russian codes but incorporates also new developments in research, mainly in fracture mechanics, and also some principal approaches used in PWR codes.Within the last upgrading and principal extending of this VERLIFE Procedure was developed within the 3-years IAEA project (in close co-operation with another project of the 6th Framework Program of the European Union “NULIFE – Plant Life Management of NPPs”) that started in 2009 with final approval and editing in 2013”) a part dealing with the evaluation of reactor internals lifetime was elaborated.. This IAEA VERLIFE procedure for internals has been implemented into the existing Normative Technical Documentation (NTD) ASI (Czech Association of Mechanical Engineers), Section IV – Evaluation of Residual Lifetime of Components and Piping in WWER type NPPs. Main damaging mechanisms that should be taken into account in reactor internals and the procedure are described in detail with necessary formulae for materials of internals: - Radiation hardening - Radiation embrittlement - Radiation swelling - Radiation creep - Swelling under stress effect - Swelling inducing embrittlement - Irradiated assisted stress corrosion cracking - Transformation austenite-ferrite and also the method for evaluation of the resistance against non-ductile failure of postulated defect. The paper will describe these main principles and also more detailed information on the procedure for evaluation of reactor internals will be given.

Druh

D - Stať ve sborníku

CEP obor

—

OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

—

Návaznosti

N - Vyzkumna aktivita podporovana z neverejnych zdroju

Rok uplatnění

2018

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název statě ve sborníku

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP Volume 1A-2018, 2018

ISBN

978-079185158-6

ISSN

0277-027X

e-ISSN

—

Počet stran výsledku

5

Strana od-do

1-5

Název nakladatele

ASME

Místo vydání

—

Místo konání akce

Praha

Datum konání akce

20. 7. 2018

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

—